ML20003D035
| ML20003D035 | |
| Person / Time | |
|---|---|
| Issue date: | 02/28/1981 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| References | |
| TASK-OS, TASK-SC-721-4 REGGD-01.147, REGGD-1.147, NUDOCS 8103181109 | |
| Download: ML20003D035 (4) | |
Text
-
Fsbruiry 1981
/m%'o U.S. NUCLEAR REGULATORY COMMISSION e
n Qg/] REGULATO'RY GUIDE
'\\..e OFFICE OF STANDARDS DEVELOPMENT e
REGULATORY GUIDE 1.147 (Task SC 7214)
INSERVICE INSPECTION CODE CASE ACCEPTABILITY ASME SEC TION XI DIVISION 1 A. INTRODl'CTION This regulatory guide lists those Section XI ASME Code Cases that are generally acceptable to the NRC staff for Section 50.55a, " Codes and Standards," of 10 CFR implementation in the inservice inspection of light-water-Part 50, " Domestic Licensing of Produc' ion and Utilization cooled nuclear power plants.
Facilities," requires, in part, that each operating license for a boiling or pressurized water-cooled nucl3ar power facility B. DISCUSSION and each construction rermit for a utilization facility be subject to the conditions ir. paragraph (g)," Inservice inspec-The ASME Boiler and Pressure Vessel Committee pub-tion Requirements," of @ 50.552. Paragraph (g) requires,in Lhes a document entitled " Code Cases."'
Generally, part, that Classes 1 2, and 3 components and their supports the individual Code Cases that make up this document meet the requirements of Section XI, " Rules for Inservice explain the intent of Code rules or provide for alternative inspection of Nuclear Power Plant Components,"' of the requirements under special circumstances.
American Sociny of Mechar;ical Engineers ( ASME) Boiler and Pressure Vessel Code or equkalent quality standards.
Most Code Cases are eventually superseded by reusion Paragraph 50.55atb), in part, references the latest editions of the Code and then are annulled by action of the ASME and addenda in effect of Section XI of the Code and any Council. In such instances, the intent of the annulled Code supplementary requirements to that section of the Code.
Case becomes part of the revised Code, and therefore Footnote 6 to $ 50.55a states that the use of specific Code continued use of the Code Case intent is sanctioned under
~
Cases may be authorized by the Commission upon request the rules of the Code. In other instances, the Cae Case is pursuant to paragraph 50.55a(aX2Xii), which requires that annulled because it is no longer acceptable or there is no proposed alternatives to the described requirements or further requirement for it. A Code Case that w1s approved portions thereof provide an acceptable level M quality and for a particular situation and not for a generic application sa fety.
should be used only for the approved situation because annulment of such a Code Case could result in situations General Design Critenon I, " Quality Standards and Re-that would not meet Code requirements. The ASME cords," of Appendix A, " General Design Criteria fo? Nuclear considers the use of Code Cases to be optional for the user Power Plants," to 10 CFR Part 50 requires, in part, that and not a mandatory requirement.
structures, systems, and components important to safety be designed, fabricated, erected, and tested to quality standards The Code Cases listed in this guide are limited to those commemrate with the importance of the safety function cases applicable to Section XI of the Code.
to be perfotmed. Where genertly recognized codes and standards are used. Criterion I requires that they be identi-All published Code Cases that are applicable to Section XI tied and evaluat:d to determine their applicability, adequacy, of the Code and were in cffect on March I8,1980, were and sufficiency and be supplemented or modified as acces-reviewed for inclusion in this guide. Code Cases that are not sary to ensure a quality productin keeping with the required listed herein tre either not endorsed or will require supple-safety function.
mentary provisions on a: individual plant basis to attain endorsement status.
The endorsement of a Code Case by thisguide constitutes LS[e E
eer ns
- nter, sat h t eet, e En e
N. Y. t oo t 7.
acceptance of its technical position for applications not of t e Commission.
USNRC REGULATORY GUlOES Comments snould be sent te the Secretary U.S. Nuclear Requsatory Commrssion, Wasningto"n. D.C. 205 5 5.
Regulatory Goldes are issued to describe and make available to the Attentions Doceseting and Service Orancn.
DuDHC methods acteptable to tne NRC staff of implementing specific Darts of tne commissaon's regulations, to des 6neate teen-Tne guides are issued in the follow.ng ten oroad divisions:
[
encues used by tne staff in evaluating specific proetems or postu.
lated accidents. or to Drovide gu6 dance to 3DDilCants. Regulatory
- 1. Dower Reactors
- a. Products 4
Guaces are not suestitutes for regulations, and comotsance witn
- 2. Aesearcn and Test Reactors
- 7. Transcortation
/
them 6: not reQuered. Niethods and solutions different from tecie set a %efs and *Aatettats FaC68aties
- 8. Cc ucational Heavth out in the quedes ewill os aCCeDiaDie if tney Drov6de a Dasss for tne
- 4. Env.ronmental and $ating
- 9. Antitrust and Onancial d eview finderus recussate to tfie issuance or continuance of a permat or
- s. N1ateriais and P' ant Protection t o. General license by the Commesstor' Cooses af issued guides may we purchased at tnecurrent Government Cornments and suggestions for improvements in these guides are Printing Of fice Drace. A suoscrsction service for future guides in sco-encourageJ at aH times, and guides will ne revised, as appa ooriate, cific devessons is avaslaole tnrougn the Government PrMtMg Office, to accommodate comments and to reflect new infor" atton of Informatinn on the sucscription service and current GPO Drices may sisDettence. Tms guide was revtsed as a result of suDstantave com-De cotaineo Dy writing the U.S. Nuclear ciegulatory Commasss cn, meets received 'forr *ne Duolic and additional staf f revsew.
W asNngt on, D.C. 2055 5. Attent6on: Paibtications sales Vanager.
8108181109
precluded by regulatory or other requirements or by the Code Case 1738 (N-1IS) is acceptable subject to the recommendaiions in this or other regulatory guides. Con-following condition in addition to those conditions 3
tingent endorsement if applicable is indicated in regulatory specified in the Code Case. Replace the last W.itence position I for specific cases. However, it is the responsibil-of the " Reply" with the following: The provisions of ity of the user to make certain that no regulatory require-this Code Case may not be applied for the examina-ments are violated and that there are no conflicts with tion of clad surfaces of nozzles, including the inner other recommended limitations resulting from Code Case surface of the nozzle-to-vesselinsert welds.
usage.
N-210 3/20/78 Exemption to Hydrostatic Tests Acceptance or endorsement by the NRC staff applies After Repairs,Section XI, Divi-only to those Code Cases or Code Case revisions with the sion I date of " Council Approval" as shown in the regulatory position of this guide. Earlier or later revisions of a Code Code Case N-210 is acceptable subject to the following Case are not endorsed by this guide. New Code Dses will condition in addition to those conditions specified in require evaluation by the NRC staff to determine if they the Code Case. Replace paragraph (3) of the " Reply" qualify for inclusion in the approved list. Because of the con-with the following: Repairs to piping, pumps, and tinuing change in the status of Code Cases,it is planned that valves where the depth of the repaired cavity does not this guide will require periodic updating to accommodate exceed 25 percent of the wall thickness.
new Code Cases and any revision of existing Code Cases.
N-211 3/20/78 Recalibratim of Ultrasmic Equip-C. REGULATORY POSITION nwnt Upon Change of Personnel,Section XI, Division i 2
- 1. The Section XI ASME Code Cases listed below (hv number, date of Council approval,3 and title) are accep N-216 31 % 78 Alternate Rules for Reactor Vessel able to the NRC staff for application in the inservice Closure Stud Examination. Sec-inspection of components and their supports for water-tion XI, Division I cooled nuclear power plants. Their use is acceptable within the limitations stated in the " Inquiry" and " Reply" sec-N 234 1/8/79 Time Between Ultrasonic Calibra-tions of each individual Cc le Case, within the limitations of tim 01ecks,Section XI, Divisim I N
such NrtC or other requirements as may exist, and within the additional limitations recommended by the NRC staff N 235 1/8/79 Ultrasonic Calibration Checks per
)
and given with the individual Code Case in the list.
Section V,Section XI, Division 1 1551 11/6/72 Inservice inspection of Welds on N-25 2 11/19/79 Low Enerfy Capacitive Discharge N-34 11/20/78 Nuclear Components,Section XI Welding Method for Temporary or Permanent Attachments to 1646 8/12/74 Partial Postponement of Cate-Componenu and Supports, See-N-72 11/20I78 gory B-C Examination forClass I tion Ill, Division 1, and XI Components,Section XI Code Case N-252isacceptable sub.ieet to the following 1647 Ul2/74 Partial Postponement of Cate-condition in addition to those conditions specified in N 73 11/20/78 gory B-D Examination for Class I the Code Case: The applicant should indicate in the Components,Section XI Safety Analysis Report the application, the material, and the thickness of the material to which the stram 1705-1 3/1/76 Ultrasonic Examination-Calibra-gage or thermocouple willbe attached by CD welding.
N 11/20/78 tion Block Tolerances,Section XI
.-278 3/I7/80 Alternative Ultrasonic Calibration 1731 11/3/75 Basic Calibration Block for Ultra-Block Configuration I 313I and
.N-Il3 11/20/78 sonic Examination of Welds 10 T-434.3,Section XI, Division i
's O in. Thick,Section XI.,
son !
Code Case N-278 is acceptable subject to the fo"owing conditions in addition to those conditions spCred in 1738 12/22/75 cw.nination - Acceptance Stand-the Code Case: When a universal calibration bbck is N-il8 11/20/78 ards for Surface. Indications in used and some or all of the reference holes r. larger Cladding,Section XI than the reflector holes at comparable depth recom-mended by Article IV,Section V,1980 edition of the ASME Code, a correction factor should be used to 2 A numencat intity of the Code Cases appears in the appendia.
adjust the DAC level to compensate for the larger reflector holes. Also,if the reactor pressure vessel was caseEa$NYoEdEtIe"SNm and1: e$aIeNe'y previ usly examined by using a cobentional block, a cod e
that on which the Code Case was reaffirmed by the A iME Cownc L ratio between the DAC curves c,%ined from the two 1.147-2 l
l l
t.%cks shcold be noted (for reference) with the signif.
D. IMPLEMENTATION
.n ican. 5dication data.
I The purpose of this section is to provide information to
- 2. Code e ases that were endorsed by the NRC in a pnor applicants regarding the use of this regulatory guide.
version of f as guide and were later annulled by action of
. the ASME founcil should be considered as deleted from
- 1. Except for those Code Cases that have been annulled the list of. iceptable Code Cases as of the date of the by action of the ASME Council,the NRCstaff willauthorize ASME Counc.' action that approved the annulment. Such appropnate use of the Code Cases listed in this guide under Code Cases tha. rere annulled on or after November I, regulatory position I upon specific request by the applicant 1978, are listed below by number, effective dates,' and in accordance with footnote 6 to ]$E 55a, the Codes and title.
Standards rule. Code Cases that are actually uses are to be identified in the Inservice Inspect:on Program.
1730 11/3/75 Acceptance Standards for Class 2
- 2. Code Cases to be applied during an inspection interval N-ll2 7/1/79 and 3 Components,Section XI, or Code Cases for a preservice inspection need not be Division I dranged because a subsequent revtsion of the Code Case is listed as the approved version in this guide.
1804 1/14/77 Minimum Section Thickness N-167 1/14/80 Requirements for Repair of
- 3. Code Cases to be applied during an ins.oection interval Nozzles,Section XI, Division I or Code Cases for a preservice mspection that were previously approved for use need not be changed because the Ccde Case has been subsequently annulled.
- 3. Code Cases that are not on the approved list of this guide (paragrsph C.1) or other regulatory guides, or for
- 4. Code Cases on the approved list may be applied to j
which authorization by the Ccemission has not been procedures for an inspection interval and procedures for the granted, are not acceptable on a p..ric basts.
inservice inspection that were established prior to the effective date of the Code Case within the limits specified Eartier date-date code crie was arproved t'y ASME Counca:
jn the Code Case and applicable regulations or recommended 4
later date-date Code case was annuned.
In other regula:ory guides.
3 i
l 1.!47-3 i
(
m.
APPENDIX Numerical Listing of Code Cases 1551
( N-34)
N-210 1646 (N-72)
N-211 1647 (N-73)
N-216 1705-1 ( N-98)
N-234 1731 (N-113)
N-235 1738 (N-118)
N-252 N-278 UNITED STATES NUCLE AR REGULATORY COMMISSION F
WASHINGTON, D. C. 20555 u.s. Nucts An msGuL ATon y OFFICI AL BUSINESS COMMession PEN ALTY FOR PRIVATE USE, $300 L
J I
i i
w h
1.147-4 l